CN108537424A - A kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure - Google Patents
A kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure Download PDFInfo
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- 238000004364 calculation method Methods 0.000 claims description 7
- 238000005202 decontamination Methods 0.000 claims description 7
- 230000003588 decontaminative effect Effects 0.000 claims description 7
- 239000011261 inert gas Substances 0.000 claims description 7
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- 239000000203 mixture Substances 0.000 claims description 2
- 230000006911 nucleation Effects 0.000 claims 3
- 238000010899 nucleation Methods 0.000 claims 3
- 238000002386 leaching Methods 0.000 claims 1
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Abstract
The present invention relates to radiation safety fields, and in particular to a kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure, this approach includes the following steps：(1) the release share based on reactor balanced recycle longevity end of term reactor core burden and radionuclide from reactor core to containment air calculates the nucleic initial activity activity that reactor core is discharged into containment air；(2) nucleic is divided into three classes according to decay mode, migrated in containment according to the initial value of radionuclide in containment air and nucleic, release during generation item and abatement item, the radioactive activity of each nucleic of different time in classified calculating containment air；(3) radionuclide specific activity in the containment air obtained according to containment leak rate and step (2), the radionuclide specific activity that integral and calculating can be discharged into environment.Computational methods provided by the invention consider complete nucleic decay chain, scientific and reasonable, versatile.
Description
Technical field
The present invention relates to radiation safety field, more particularly to a kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms are commented
Estimate method.
Background technology
Radio nuclide source terms are the important input datas for assessing irradiation dose suffered by the public in nuclear power plant's accident, are nuclear power plant's peaces
The content paid close attention in complete analysis and environmental impact assessment.After loss of-coolant accident (LOCA) (LOCA) occurs for PWR nuclear power plant, fuel rod
Enter containment headroom with the radionuclide in primary Ioops coolant, by systems such as itself decay, deposition, spray removals
After row process, radionuclide is by the way that in containment leak to environment, radiation hazradial bundle is caused to the public and biology.In LOCA accident
Radionuclide migration and release process are as shown in Figure 1.
At present when calculating radionuclide specific activity in nuclear power plant's LOCA containments, a kind of calculating mould of simplification of generally use
Type, as shown in formula (1).However, due to different reactor heap-type, reactor core release type, release time, nucleic removal machine
The decay mode of the different and nucleic itself such as system is different, and formula (1) is caused to be not particularly suited for the nuclear power plant of different heap-type
And all types of radionuclide specific activities calculate.
Wherein, Ai(t) radioactive activity of any time period containment headroom Radionuclide i, Bq during being LOCA accident；
λiFor the decay coefficient of radionuclide i, s-1；λTiFor total removal constant of nucleic i in containment, including ad hoc removal, nature
Removal, leakage etc., s-1。
In npp safety analysis, often uses some hypothesis to simplify and calculates, such as when calculating LOCA accident source item,
The contribution that parent nucleus decays to daughter nucleus source item is not considered；Nuclear power plant for containment spray system as engineered safeguards features, peace
The spray removal of full shell interior element iodine considers according to instantaneous removal, and in practical nuclear power plant LOCA containment spray system removal
Effect is not unconfined, it is impossible to which the Airborne fission products that will be dispersed in containment, especially iodine instantaneously reach setting
Removal efficiency, but need an effective removal process.
Since nuclear power plant requires conservative in designing and evaluating, radio nuclide source terms design value should be able to wrap in the case of accident
The least favorable situation being likely to occur in network operation.In conjunction with the requirement of national relevant laws and regulations directive/guide and Shen Guan authorities, for presurized water reactor
Design of nuclear power plant feature, there is an urgent need for propose a set of improved PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure to calculate
Different time is discharged into all kinds of nuclide radiation quality activity of containment and environment after accident, is evaluated with meeting nuclear power plant's radiation safety
And the demand of nuclear power independent research design.
Invention content
The object of the present invention is to provide a kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedures, existing to solve
There are versatility and Conservative Property existing for technology.
Technical scheme is as follows：A kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure, including
Following steps：
(1) based on reactor balanced recycle longevity end of term reactor core burden and radionuclide from reactor core to containment air
Share is discharged, the nucleic initial activity activity that reactor core is discharged into containment air is calculated；
(2) it migrated in containment, discharged according to the initial value of radionuclide in containment air and radionuclide
Generation item in journey and abatement item, calculate the radioactive activity of nucleic in the case of different time in containment air；
(3) radionuclide specific activity in the containment air obtained according to containment leak rate and step (2), integral and calculating
The nuclide radiation quality activity that can be discharged into environment.
Further, in step (1), the release of reactor fuel stick involucrum carrys out radioactivity after assessment accident according to time unrelated procedures
Activity considers that the radionuclide abrupt release in reactor fuel pellet-clad gap is mixed to containment and uniformly.From
The radionuclide specific activity calculating that reactor core is discharged into containment is multiplied by respectively based on the end of term in balanced recycle longevity reactor core burden
The release share of a nucleic also needs the fractions distribution according to iodine for iodine, and it is corresponding to be multiplied by molecular iodine, organic iodine and particle iodine
Form percentage.
Further, in step (2), the initial value source of radionuclide includes that primary Ioops coolant is released in containment air
It puts and is discharged with reactor fuel stick involucrum, wherein the radionuclide specific activity in primary Ioops coolant and putting in reactor fuel stick
Penetrating property activity is compared, small several orders of magnitude, negligible when calculating.The generation item of radionuclide declines for parent nucleus in containment
Become, abatement item is different because of nucleic, and for iodine, abatement item includes nucleic itself decay, deposition, container spray, leakage etc.；For
Inert gas, abatement item include nucleic itself decay and containment leak.When calculating nuclide radiation quality activity, due to considering to decline
Become the contribution that parent nucleus decays to daughter nucleus in chain, therefore according to the decay mode of nucleic, nucleic is divided into three classes, establishes differential respectively
Equation, it is as follows：
● simple decay
Wherein,
Ai(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq；
λiFor the decay coefficient of radionuclide i, s-1；
λdiFor (t after accidentn-1, tn) the removal constant of radionuclide i, s in period inner containment-1, for indifferent gas
Body, λdi=0；
λ0For (t after accidentn-1, tn) period inner containment slip, s-1。
Such nucleic includes131I、132I、133I、134I、135I、85mKr、87Kr、88Kr、138Xe、134Cs、136Cs etc..
● series disintegraton
Aj(tn) it is t after accidentnWhen containment in nucleic j radioactive activity, Bq；
λjFor the decay coefficient of radionuclide j, s-1；
λdjFor (t after accidentn-1, tn) the removal constant of radionuclide j, s in period inner containment-1, for indifferent gas
Body, λdj=0；
ξi1The branching ratio for being nucleic j for radionuclide i decays.
Such nucleic includes85Kr,131mXe、133mXe、135mXe etc..For the nucleic that parent nucleus is iodine, such as131mXe, due to iodine
It is divided into three kinds of elemental iodine, organic iodine, particle iodine forms, the decay tribute for needing the form according to parent nucleus to calculate separately it to the nucleic
It offers, the radioactive activity of final nucleic is the sum of following four part：
1. the nucleic j radioactive activities discharged from reactor core；
2. the nucleic j radioactive activities generated by elemental iodine decay；
3. the nucleic j radioactive activities generated by organic iodine decay；
4. the nucleic j radioactive activities generated by the decay of particle iodine.
● complexity decay
Wherein,
Ak(tn) it is t after accidentnWhen containment in nucleic k radioactive activity, Bq；
λkFor the decay coefficient of radionuclide k, s-1；
λdkFor (t after accidentn-1, tn) the removal constant of radionuclide k, s in period inner containment-1, for indifferent gas
Body, λdk=0；
ξi2The branching ratio for being nucleic k for radionuclide i decays；
ξjThe branching ratio for being nucleic k for radionuclide j decays.
Such nucleic includes133Xe、135Xe etc..In containment133Xe、135Xe includes what reactor core discharged133Xe、135Xe is put
Penetrating property activity,133mXe、135mXe is decayed into133Xe、135The radioactive activity of Xe, reactor core discharge133I、135I is decayed into133Xe、135The radioactive activity etc. of Xe, wherein iodine are divided into elemental iodine, organic iodine and particle iodine, therefore in containment133Xe、135Xe's puts
Penetrating property activity is the sum of following five part：
1. the nucleic k radioactive activities discharged from reactor core；
2. the nucleic k radioactive activities (A that the nucleic j decays discharged from reactor core generatej→Ak)；
3. the nucleic k radioactive activities (A generated by elemental iodine decayi→Ak) and nucleic j is decayed by elemental iodine decay again
At the radioactive activity (A of nucleic ki→Aj→Ak)；
4. the nucleic k radioactive activities (A generated by organic iodine decayi→Ak) and nucleic j is decayed by organic iodine decay again
At the radioactive activity (A of nucleic ki→Aj→Ak)；
5. the nucleic k radioactive activities (A generated by the decay of particle iodinei→Ak) and nucleic j is decayed by particle iodine decay again
At the radioactive activity (A of nucleic ki→Aj→Ak)。
When calculating the radioactive activity of iodine in containment, either engineered safeguards features act on the removal of iodine, still
The natural removal process of iodine, be required to first to determine elemental iodine effectively removes the time.Removal constant based on elemental iodine and maximum
The time calculation formula that effectively removes of decontamination factor, containment interior element iodine is：
Wherein,
T effectively removes the time for elemental iodine；
DF is the maximum decontamination factor of elemental iodine；
λdFor the removal constant of elemental iodine.
Further, in step (3), the radionuclide that can be discharged into environment comes from the leakage of containment, once nucleic
It can be discharged into environment, decay and the deposition of nucleic itself will not be considered any further when calculating radionuclide specific activity.According to containment
The radioactive activity of nucleic, the nuclide radiation quality activity meter that can be discharged into environment in the containment that slip and step (2) calculate
It calculates shown in equation such as formula (6), the equation is suitable for the nucleic of above-mentioned three kinds of decay modes.
Wherein,
For (t after accidentn-1, tn) it can be discharged into environment the radioactive activity of nucleic i, Bq in the period；
Ai(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq.
The nuclide radiation quality activity that can be discharged into environment in each period is summed it up to get to being discharged into environment after accident
In nucleic cumulated activity activity.
Beneficial effects of the present invention are as follows：
1) it is based on complete nucleic decay chain, considers contribution of the accident stepmother nuclear decay to sub- nuclear activity activity, classification
The activity of each nucleic in decay chain is calculated, result of calculation is more reasonable.
2) it is put forward for the first time the process feature of engineered safeguards features (spray system) removal elemental iodine, it is determined that elemental iodine has
Effect removal time computational methods, rather than removed according to moment, it is more conform with actual conditions；
3) when proposing the initial Activity Calculation of radionuclide in containment air, fuel pellet and putting in involucrum gap
Penetrating property nucleic is thought of as moment and enters containment air and uniformly mix.
4) according to the migration of accident Radionuclide and release process, quantify respectively containment and environment Radionuclide generation item and
Cut down item, and the time after accident is divided into several periods, progressive alternate calculates, and provides a kind of general presurized water reactor mistake
Water accident radio nuclide source terms computational methods.
Description of the drawings
Attached drawing described herein is used to provide further understanding of the present invention, and constitutes the part of the present invention.Attached
In figure：
Fig. 1 is migration and the release process schematic of presurized water reactor loss of-coolant accident (LOCA) radionuclide of the present invention；
Fig. 2 is the simple decay process figure of specific embodiment of the invention Radionuclide；
Fig. 3 is specific embodiment of the invention Radionuclide series disintegraton procedure chart；
Fig. 4 is specific embodiment of the invention Radionuclide complexity decay process figure.
Specific implementation mode
The invention will be further described with reference to the accompanying drawings and detailed description.
A kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure provided by the invention includes mainly following step
Suddenly：
(1) reactor core is discharged into the nucleic initial activity Activity Calculation in containment air
Consider that the radionuclide abrupt release in reactor fuel pellet-clad gap is mixed to containment and uniformly.It adopts
It is multiplied by release share of each nucleic from reactor core to containment air with reactor balanced recycle longevity end of term reactor core burden, is obtained
It is discharged into the radionuclide specific activity initial value of containment from reactor core, for iodine, molecule need to be multiplied by according to the fractions distribution of iodine
Iodine, organic iodine and the corresponding form percentage of particle iodine.Wherein, the end of term in reactor balanced recycle longevity reactor core burden is by SCALE
Program is calculated, and as nuclear power plant other design parameters, belongs to the upstream input that radionuclide specific activity after accident calculates
Parameter.
(2) nucleic radioactive activity measuring meter is calculated in different time containment after accident
According to the radioactive activity initial value of containment air Radionuclide and nucleic during containment is migrated, discharged
It generates item and cuts down item, the radioactive activity of different time containment air Radionuclide after calculating accident.
The initial value source of radionuclide includes the release of primary Ioops coolant and reactor fuel stick packet in containment air
Shell discharges, wherein the radionuclide specific activity in primary Ioops coolant is small compared with the radioactive activity in reactor fuel stick
Several orders of magnitude, it is negligible when calculating.The generation item of radionuclide is mainly the decay of parent nucleus in decay chain in containment,
It is different because of nucleic to cut down item, for iodine, abatement item includes nucleic itself decay, deposition, container spray, leakage etc.；For lazy
Property gas, abatement item include nucleic itself decay and containment leak.
When calculating nucleic activity, several periods (t is divided the time inton-1, tn), the nuclide emission in each period
Property activity is iterated calculating.The time step of division, consider aerosol removal constant change with time, elemental iodine
Remove the time, nuclide radiation quality activity exports the factors such as the timing node of result.Due to considering parent nucleus decay antithetical phrase in decay chain
The contribution of core, it is therefore desirable to according to the decay mode of nucleic, nucleic is divided into simple decay, series disintegraton, complicated decay three classes,
The differential equation is established respectively, it is as follows：
● simple decay
For the nucleic simply to decay, decay process is as shown in Figure 2.Such nucleic after reactor core is discharged into containment,
By engineered safeguards features removal or natural removal (except inert gas), containment leak in itself decay abatement, containment
Etc. processes, can be discharged into environment.Such nucleic includes131I、132I、133I、134I、135I、85mKr、87Kr、88Kr、138Xe、134Cs
、136Cs etc..The differential equation is built to such nuclide radiation quality activity in containment, as shown in formula (7), formula (7) are solved
Obtain formula (8).
Wherein,
Ai(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq；
Ai(tn-1) it is t after accidentn-1When containment in nucleic i radioactive activity, Bq；
λiFor the decay coefficient of radionuclide i, s-1；
λdiFor (t after accidentn-1, tn) the removal constant of radionuclide i, s in period inner containment-1, for indifferent gas
Body, λdi=0；
λ0For (t after accidentn-1, tn) period inner containment slip, s-1。
● series disintegraton
For the nucleic of series disintegraton, decay process is as shown in Figure 3.Such nucleic after reactor core is discharged into containment,
Generate the decay of item parent nucleus in decay chain, abatement item includes itself decay, in containment engineered safeguards features removal or from
So removal (except inert gas), containment leak etc..Such nucleic includes85Kr,131mXe、133mXe、135mXe etc..To containment
Such interior nuclide radiation quality activity builds the differential equation, and as shown in formula (9), formula (10) is obtained to formula (9) solution.
Wherein,
Aj(tn) it is t after accidentnWhen containment in nucleic j radioactive activity, Bq；
Aj(tn-1) it is t after accidentn-1When containment in nucleic j radioactive activity, Bq；
λjFor the decay coefficient of radionuclide j, s-1；
λdjFor (t after accidentn-1, tn) the removal constant of radionuclide j, s in period inner containment-1, for indifferent gas
Body, λdj=0；
ξi1The branching ratio for being nucleic j for radionuclide i decays.
For the nucleic that parent nucleus is iodine, such as131mXe, because parent nucleus iodine is divided into three kinds of elemental iodine, organic iodine, particle iodine shapes
State needs the form according to parent nucleus to calculate separately it and contributes the decay of the nucleic, the radioactive activity of final nucleic include with
Lower four parts, sum after being calculated separately according to formula (10)：
1. the nucleic j radioactive activities discharged from reactor core；
2. the nucleic j radioactive activities generated by elemental iodine decay；
3. the nucleic j radioactive activities generated by organic iodine decay；
4. the nucleic j radioactive activities generated by the decay of particle iodine.
● complexity decay
For the nucleic of complexity decay, decay process is as shown in Figure 4.Such nucleic after reactor core is discharged into containment,
Generate the decay of item parent nucleus in decay chain, abatement item includes itself decay, in containment engineered safeguards features removal or from
So removal (except inert gas), containment leak etc..Such nucleic includes133Xe、135Xe etc..To such nucleic in containment
Radioactive activity builds the differential equation, and as shown in formula (11), formula (12) is obtained to formula (11) solution.
Wherein,
Ak(tn) it is t after accidentnWhen containment in nucleic k radioactive activity, Bq；
Ak(tn-1) it is t after accidentn-1When containment in nucleic k radioactive activity, Bq；
λkFor the decay coefficient of radionuclide k, s-1；
λdkFor (t after accidentn-1, tn) the removal constant of radionuclide k, s in period inner containment-1, for indifferent gas
Body, λdk=0；
ξi2The branching ratio for being nucleic k for radionuclide i decays；
ξjThe branching ratio for being nucleic k for radionuclide j decays.
For in containment133Xe、135Xe, including reactor core release133Xe、135Xe radioactive activities,133mXe、135mXe
It decays into133Xe、135The radioactive activity of Xe, reactor core discharge133I、135I is decayed into133Xe、135The radioactive activity etc. of Xe,
Middle iodine is divided into elemental iodine, organic iodine and particle iodine, therefore in containment133Xe、135The radioactive activity of Xe is by following five part group
At summing after being calculated separately according to formula (12)：
1. the nucleic k radioactive activities discharged from reactor core；
2. the nucleic k radioactive activities (A that the nucleic j decays discharged from reactor core generatej→Ak)；
3. the nucleic k radioactive activities (A generated by elemental iodine decayi→Ak) and nucleic j is decayed by elemental iodine decay again
At the radioactive activity (A of nucleic ki→Aj→Ak)；
4. the nucleic k radioactive activities (A generated by organic iodine decayi→Ak) and nucleic j is decayed by organic iodine decay again
At the radioactive activity (A of nucleic ki→Aj→Ak)；
5. the nucleic k radioactive activities (A generated by the decay of particle iodinei→Ak) and nucleic j is decayed by particle iodine decay again
At the radioactive activity (A of nucleic ki→Aj→Ak)。
Certainly for the radioactive nuclide iodine in containment, either removal effect, or deposition of engineered safeguards features etc.
Right removal effect, the removal of elemental iodine is not unconfined, sets maximum decontamination factor, therefore calculating radioactive activity
When, it is necessary first to determine elemental iodine effectively removes the time.Transport process based on elemental iodine, removal constant and maximum decontamination because
The time that effectively removes of son, containment interior element iodine calculates as shown in formula (13).
Wherein,
T effectively removes the time for elemental iodine；
DF is the maximum decontamination factor of elemental iodine；
λdFor the removal constant of elemental iodine.
(3) environment Radionuclide radioactive activity calculates
Radionuclide in environment comes from the leakage of containment, once nucleic can be discharged into environment, is radiated calculating
Decay and the deposition of nucleic itself will not be considered any further when property activity.Radioactivity based on nucleic in containment leak rate and containment
Activity, the nuclide radiation quality Activity Calculation equation in constructing environment, as shown in formula (14), the equation is suitable for three kinds of decays
The nucleic of type.
Wherein,
For (t after accidentn-1, tn) radioactive activity of nucleic i that can be discharged into environment in the period, Bq；
Ai(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq.
For the radionuclide that parent nucleus is iodine, the difference that merotomizes according to the form of reactor core release and iodine is also needed
Summation obtains after calculatingThen the nuclide radiation quality activity that can be discharged into environment in each period is summed it up, obtains thing
The nucleic cumulated activity activity that can be discharged into environment after therefore.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
God and range.It is all in the spirit and principles in the present invention, made by any modifications and variations belong to the claims in the present invention and its
Within the scope of equivalent technology, then the present invention is also intended to include these modifications and variations.
Claims (10)
1. a kind of PWR nuclear power plant loss of-coolant accident (LOCA) radio nuclide source terms appraisal procedure, which is characterized in that the appraisal procedure includes
Following steps：
(1) based on reactor balanced recycle longevity end of term reactor core burden and radionuclide from reactor core to the release of containment air
Share calculates the nucleic initial activity activity that reactor core is discharged into containment air；
(2) according to the initial value of radionuclide in containment air and radionuclide during containment is migrated, discharged
Generation item and abatement item, calculate the radioactive activity of nucleic in the case of different time in containment air；
(3) radionuclide specific activity in the containment air obtained according to containment leak rate and step (2), integral and calculating release
To the radionuclide specific activity in environment.
2. according to the method described in claim 1, it is characterized in that, being discharged into the radionuclide initial live of containment from reactor core
The release share that degree is multiplied by each nucleic according to the end of term in balanced recycle longevity reactor core burden calculates, and for iodine, needs basis
The fractions distribution of iodine is multiplied by molecular iodine, organic iodine and the corresponding form percentage of particle iodine.
3. according to the method described in claim 1, it is characterized in that, the generation item of radionuclide predominantly decays in containment
The decay of parent nucleus in chain, abatement item is different because of nucleic, and for iodine, abatement item includes nucleic itself decay, deposition, containment spray
Leaching, leakage etc.；For inert gas, abatement item includes nucleic itself decay and containment leak.Calculate the nucleic in containment
Consider that parent nucleus decay in decay chain effectively removes the time to the contribution of daughter nucleus and iodine when activity, it is therefore desirable to according to nucleic
Nucleic is divided into simple decay, series disintegraton, complicated decay three classes by decay mode.
4. according to the method described in claim 3, it is characterized in that, the nucleic simply to decay includes131I、132I、133I、134I、135I、85mKr、87Kr、88Kr、138Xe、134Cs、136Cs etc..It is to such nucleic activity structure differential equation in containment：
Wherein, Ai(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq；λiDecay for radionuclide i is normal
Number, s-1；λdiFor (t after accidentn-1, tn) the removal constant of radionuclide i, s in period inner containment-1；λ0After accident
(tn-1, tn) period inner containment slip, s-1。
5. according to the method described in claim 3, it is characterized in that, the nucleic of series disintegraton includes85Kr,131mXe、133mXe、135mXe etc..It is to such nuclide radiation quality activity structure differential equation in containment：
Wherein, Aj(tn) it is t after accidentnWhen containment in nucleic j radioactive activity, Bq；Ai(tn) it is t after accidentnShi Anquan
The radioactive activity of nucleic i, Bq in shell；λjFor the decay coefficient of radionuclide j, s-1；λdjFor (t after accidentn-1, tn) time
The removal constant of radionuclide j, s in section inner containment-1, for inert gas, λdj=0；λ0For (t after accidentn-1, tn) when
Between section inner containment slip, s-1；ξi1The branching ratio for being nucleic j for radionuclide i decays.
6. according to the method described in claim 5, it is characterized in that, since iodine is divided into three kinds of elemental iodine, organic iodine, particle iodine shapes
State, therefore the nucleic that parent nucleus is iodine, such as131mXe, the decay tribute for needing the form according to parent nucleus to calculate separately parent nucleus to the nucleic
It offers, the radioactive activity of final nucleic is the sum of following four part：
1. the nucleic j radioactive activities discharged from reactor core；
2. the nucleic j radioactive activities generated by elemental iodine decay；
3. the nucleic j radioactive activities generated by organic iodine decay；
4. the nucleic j radioactive activities generated by the decay of particle iodine.
7. according to the method described in claim 3, it is characterized in that, the nucleic of complicated decay includes133Xe、135Xe etc..To safety
Such nuclide radiation quality activity structure differential equation is in shell：
Wherein, Ak(tn) it is t after accidentnWhen containment in nucleic k radioactive activity, Bq；Aj(tn) it is t after accidentnShi Anquan
The radioactive activity of nucleic j, Bq in shell；Ai(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq；λkTo put
The decay coefficient of penetrating property nucleic k, s-1；λdkFor (t after accidentn-1, tn) in period inner containment the removal of radionuclide k it is normal
Number, s-1, for inert gas, λdk=0；λ0For (t after accidentn-1, tn) period inner containment slip, s-1；ξi2For radiation
Property nucleic i decay be nucleic k branching ratio；ξjThe branching ratio for being nucleic k for radionuclide j decays.
8. the method according to the description of claim 7 is characterized in that in containment133Xe、135Xe activity includes reactor core release
's133Xe、135Xe radioactive activities,133mXe、135mXe is decayed into133Xe、135The radioactive activity of Xe, reactor core discharge133I、135I
It decays into133Xe、135The radioactive activity etc. of Xe, wherein iodine are divided into elemental iodine, organic iodine and particle iodine, therefore in containment133Xe、135The radioactive activity of Xe is the sum of following five part composition：
1. the nucleic k radioactive activities discharged from reactor core；
2. the nucleic k radioactive activities (A that the nucleic j decays discharged from reactor core generatej→Ak)；
3. the nucleic k radioactive activities (A generated by elemental iodine decayi→Ak) and nucleic j is decayed by elemental iodine decay again nucleation
Radioactive activity (the A of plain ki→Aj→Ak)；
4. the nucleic k radioactive activities (A generated by organic iodine decayi→Ak) and nucleic j is decayed by organic iodine decay again nucleation
Radioactive activity (the A of plain ki→Aj→Ak)；
5. the nucleic k radioactive activities (A generated by the decay of particle iodinei→Ak) and nucleic j is decayed by particle iodine decay again nucleation
Radioactive activity (the A of plain ki→Aj→Ak)。
9. according to the method described in claim 3, it is characterized in that, containment interior element iodine effectively removes the time according to iodine
Transport process, removal constant and maximum decontamination factor calculate, and calculation formula is as follows：
Wherein, t effectively removes the time for elemental iodine；DF is the maximum decontamination factor of elemental iodine；λdIt is normal for the removal of elemental iodine
Number.
10. according to the method described in claim 1, it is characterized in that, when nuclide radiation quality activity in computing environment will no longer
Consider decay and the deposition of nucleic itself.Based on the radioactive activity of nucleic in containment leak rate and containment, constructing environment
In nuclide radiation quality Activity Calculation equation it is as follows, the equation be suitable for three kinds of decay modes nucleic.
Wherein,For (t after accidentn-1, tn) radioactive activity of nucleic i that can be discharged into environment in the period, Bq；Ai
(tn) it is t after accidentnWhen containment in nucleic i radioactive activity, Bq.
For the radionuclide that parent nucleus is iodine, also needing to be merotomized according to the form of reactor core release and iodine calculates separately
Summation obtains afterwardsThen the nuclide radiation quality activity that can be discharged into environment in each period is summed it up, after obtaining accident
The nucleic cumulated activity activity that can be discharged into environment.
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